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Okuno, Hiroshi; Yamamoto, Kazuya
JAEA-Review 2020-066, 32 Pages, 2021/02
JAEA-Review-2020-066.pdf:3.01MB
The International Atomic Energy Agency (abbreviated as IAEA) has been implementing the Asian Nuclear Safety Network (abbreviated as ANSN) activities since 2002. As part of this effort, Topical Group on Emergency Preparedness and Response (abbreviated as EPRTG) for nuclear or radiation disasters was established in 2006 under the umbrella of the ANSN. Based on the EPRTG proposal, the IAEA conducted 23 Asian regional workshops in the 12 years from 2006 to 2017. Typical topical fields of the regional workshops were nuclear emergency drills, emergency medical care, long-term response after nuclear/radiological emergency, international cooperation, national nuclear disaster prevention system. The Japan Atomic Energy Agency has produced coordinators for EPRTG since its establishment and has led its activities since then. This report summarizes the Asian regional workshops conducted by the IAEA based on the recommendations of the EPRTG.
Saito, Tatsuo; Kobayashi, Shinichi*; Zaitsu, Tomohisa*; Shimo, Michikuni*; Fumoto, Hiromichi*
Hoken Butsuri (Internet), 55(2), p.86 - 91, 2020/06
Safety cases for disposal of uranium bearing waste and NORM with uranium has not yet been fully developed in Japan, because of safety assessment of extraordinary long timespan and uncertainty in unexpected incidents with uncompleted radon impact evaluation measures arising from uranium waste disposal facility in far future. Our task group of radiation protection for wastes with natural radioactive nuclides studied some safety cases with disposal of uranium bearing waste and NORM in terms of nuclides, U-235, U-238 and their progenies, and comprehensively discussed the current state of their disposal in comparison to the ideas of international organizations such as ICRP and IAEA. We developed our ideas for long term uncertainty and radon with the knowledge of experts in each related area of direction, repeating discussions, focusing out the orientation of each directions, and outlined the recommendations with our suggestions of solving important issues in the future to be addressed.
Toguri, Satohito*; Yahagi, Ryoji*; Okihara, Mitsunobu*; Takeuchi, Nobumitsu*; Kurosaki, Hiromi*; Matsui, Hiroya
JAEA-Technology 2018-017, 161 Pages, 2019/03
JAEA-Technology-2018-017.pdf:28.26MB
The Japan Atomic Energy Agency has been conducting research on three critical issues for development of: engineering techniques for underground construction, modelling techniques of mass transfer and tunnel backfilling methods at the Mizunami Underground Research Laboratory on the basis of Medium to Long-Term Plan of Japan Atomic Energy Agency. This report describes the overall plan of in-situ test to backfill a part of Mizunami Underground Research Laboratory, which is planned for "development of tunnel backfilling method".
Ho, H. Q.; Honda, Yuki*; Hamamoto, Shimpei; Ishii, Toshiaki; Fujimoto, Nozomu*; Ishitsuka, Etsuo
Applied Radiation and Isotopes, 140, p.209 - 214, 2018/10
Times Cited Count：3 Percentile：29.78(Chemistry, Inorganic & Nuclear)Hamuza, E.-A.; Nagai, Haruyasu; Sagara, Hiroshi*
Energy Procedia, 131, p.279 - 284, 2017/12
Times Cited Count：1 Percentile：61.03(Energy & Fuels)In this study we would like to propose a method to use atmospheric dispersion simulations by WSPEEDI for consideration of crisis management on radionuclide dispersion from a nuclear power plant. WSPEEDI can simulate and output crucial information regarding environmental distribution of radionuclides and weather pattern for nuclear emergency countermeasures, thus this study will make use of its output to display the effective information for evacuation planning from a radionuclide dispersion. We will be assembling database of atmospheric dispersion outputs for one year by using WSPEEDI for a nuclear facility, then the database will be analysed to make the summary that has useful information for nuclear emergency managements. WSPEEDI outputs are converted into numeric information showing dispersion characteristics so that users can understand WSPEEDI predictions easily.
Kawaguchi, Kenji*; Maruyama, Yu; Zheng, X.
Journal of Artificial Intelligence Research, 56, p.153 - 195, 2016/06
Times Cited Count：12 Percentile：54.4(Computer Science, Artificial Intelligence)Kumada, Hiroaki; Yamamoto, Kazuyoshi; Yamamoto, Tetsuya*; Nakai, Kei*; Nakagawa, Yoshinobu*; Kageji, Teruyoshi*; Matsumura, Akira*
Applied Radiation and Isotopes, 61(5), p.1045 - 1050, 2004/11
Times Cited Count：12 Percentile：61.44(Chemistry, Inorganic & Nuclear)To carry out the BNCT clinical trials based on accurate dosimetry of several absorbed doses given to a patient, we have developed JCDS which can determine the absorbed doses by numerical simulation. The aim of this study is to improve the accuracy of the BNCT dosimetry efficiently. We have developed the multi-voxel calculation method reconstructing the original voxel model by combining of several voxel cell sizes such as in 5mm, 10mm and 20mm voxel cell. To verify the accuracy of the multi-voxel method, the calculation results were compared with the phantom experimental data. These results proved that the multi-voxel calculation enables JCDS to more accurately estimate the absorbed doses to a patient by efficient calculations.
Kumada, Hiroaki; Yamamoto, Kazuyoshi; Torii, Yoshiya; Matsumura, Akira*; Yamamoto, Tetsuya*; Nose, Tadao*; Nakagawa, Yoshinobu*; Kageji, Teruyoshi*; Uchiyama, Junzo
JAERI-Tech 2003-002, 49 Pages, 2003/03
JAERI-Tech-2003-002.pdf:5.22MB
no abstracts in English
Yamamoto, Kazuyoshi; Kumada, Hiroaki; Kishi, Toshiaki; Torii, Yoshiya; Endo, Kiyoshi*; Yamamoto, Tetsuya*; Matsumura, Akira*; Uchiyama, Junzo; Nose, Tadao*
JAERI-Tech 2002-092, 23 Pages, 2002/12
JAERI-Tech-2002-092.pdf:5.22MB
Thermal neutron flux is determined using the gold wires in current BNCT irradiation, so evaluation of arbitrary points after the irradiation is limited in the quantity of these detectors. In order to make up for the weakness, dose estimation of a patient is simulated by a computational dose calculation supporting system. In another way without computer simulation, a medical irradiation condition can be replicate experimentally using of realistic phantom which was produced from CT images by rapid prototyping technique. This phantom was irradiated at a same JRR-4 neutron beam as clinical irradiation condition of the patient and the thermal neutron distribution on the brain surface was measured in detail. This experimental evaluation technique using a realistic phantom is applicable to in vitro cell irradiation experiments for radiation biological effects as well as in-phantom experiments for dosimetry under the nearly medical irradiation condition of patient.
Kumada, Hiroaki; Torii, Yoshiya
JAERI-Data/Code 2002-018, 158 Pages, 2002/09
JAERI-Data-Code-2002-018.pdf:30.28MB
A boron neutron capture therapy (BNCT) with epithermal neutron beam is expected to treat effectively for malignant tumor that is located deeply in the brain. It is indispensable to estimate preliminarily the irradiation dose in the brain of a patient in order to perform the epithermal neutron beam BNCT. Thus, the JAERI Computational Dosimetry System (JCDS), which can calculate the dose distributions in the brain, has been developed. JCDS is a software that creates a 3-dimentional head model of a patient by using CT and MRI images and that generates a input data file automaticly for calculation neutron flux and gamma-ray dose distribution in the brain by the Monte Carlo code: MCNP, and that displays the dose distribution on the head model for dosimetry by using the MCNP calculation results. JCDS has any advantages as follows; By treating CT data and MRI data which are medical images, a detail three-dimensional model of patinet's head is able to be made easily. The three-dimensional head image is editable to simulate the state of a head after its surgical processes such as skin flap opening and bone removal for the BNCT with craniotomy that are being performed in Japan. JCDS can provide information for the Patient Setting System to set the patient in an actual irradiation position swiftly and accurately. This report describes basic design and procedure of dosimetry, operation manual, data and library structure for JCDS (ver.1.0)
Kumada, Hiroaki; Matsumura, Akira*; Nakagawa, Yoshinobu*; Yamamoto, Tetsuya*; Yamamoto, Kazuyoshi; Torii, Yoshiya
Research and Development in Neutron Capture Therapy, p.529 - 534, 2002/09
no abstracts in English
Endo, Kiyoshi*; Matsumura, Akira*; Yamamoto, Tetsuya*; Nose, Tadao*; Yamamoto, Kazuyoshi; Kumada, Hiroaki; Kishi, Toshiaki; Torii, Yoshiya; Kashimura, Takanori*; Otake, Shinichi*
Research and Development in Neutron Capture Therapy, p.425 - 430, 2002/09
Using the Rapid Prototyping Technique, we produced a realistic phantom as a formative model of a patient head. This realistic phantom will contribute to verification of our planning system. However, cross-correlation among the calculations using the JAERI Computational Dosimetry System (JCDS), the realistic phantom, and the in vivo measurements were not fully completed because of the difficulty involved in modeling a post-surgical brain and a thermal neutron shield. The experimental simulation technique using the realistic phantom is a useful tool for more reliable dose planning for the intraoperative BNCT.
Yamamoto, Tetsuya*; Matsumura, Akira*; Yamamoto, Kazuyoshi; Kumada, Hiroaki; Torii, Yoshiya; Endo, Kiyoshi*; Matsushita, Akira*; Shibata, Yasushi*; Nose, Tadao*
Research and Development in Neutron Capture Therapy, p.415 - 418, 2002/09
Dose measurements in a patient's brain undergoing intraoperative BNCT (IOBNCT) were compared with calculations by a JAERI computational dosimetry system (JCDS). The maximum thermal neutron flux on the brain surface from the postirradiation measurement averaged 2.33
0.37(
10
cm
s
) and the vascular boron dose averaged 11.41.2 (9.6-12.7) Gy. Using JCDS, the maximum thermal neutron flux in the irradiated volume averaged 2.210.33(10cms), while the target vascular dose averaged 5.7 Gy and varied from 3.5 to 7.8 Gy. As such, in the dose planning for intra-operative irradiation, practical use of JCDS is recommended for uniform volume-dose control of postsurgical brain in IOBNCT.
Nose, Tadao*; Matsumura, Akira*; Yamamoto, Tetsuya*; Shibata, Yasushi*; Yoshida, Fumiyo*; Akutsu, Hiroyoshi*; Yasuda, Susumu*; Matsushita, Akira*; Nakai, Kei*; Yamada, Takashi*; et al.
UTRCN-G-29, p.114 - 123, 2001/00
no abstracts in English
Proc. of 1998 IEEE Int. Conf. on Control Applications (CD-ROM), p.1323 - 1327, 1998/00
no abstracts in English
Nishimori, Nobuyuki; Minehara, Eisuke; Sawamura, Masaru; Nagai, Ryoji; Kikuzawa, Nobuhiro; Sugimoto, Masayoshi; Yamauchi, Toshihiko
Proceedings of the 20th International Free Electron Laser Conference, p.II23 - II24, 1998/00
no abstracts in English
Yamamoto, Hideaki
Proc. of IAEA/KINS Nuclear Safety Symp., 0, p.26 - 31, 1996/00
no abstracts in English
Naruse, Yuji; Matsuda, Yuji; *
Fusion Engineering and Design, 12, p.293 - 317, 1990/00
Times Cited Count：78 Percentile：98.31(Nuclear Science & Technology)no abstracts in English
; *
JAERI-M 89-218, 60 Pages, 1989/12
no abstracts in English
; ; ; *; *
Source Term Evaluation for Accident Conditions, p.733 - 744, 1986/00
no abstracts in English
